ML22174A347

Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis

ML22174A347
Person / Time
Site:	Callaway
Issue date:	06/23/2022
From:	Ameren Missouri, Union Electric Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22174A345	List: ML22174A347 ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis
References
ULNRC-06753
Download: ML22174A347 (18)

Text

Enclosure 1 to ULNRC-06753 Pagelofl8 ENCLOSURE 1 PRESENTATION SLIDES FOR JUNE 29, 2022 PRE-SUBMITTAL MEETING 17 pages follow this cover sheet.

- S

• 5%S Ca11awayCSALAR Pre-Submittal Meeting

Ame ren MISSOURI Callaway Energy Center Callaway CSA LAR Pre-Submittal Meeting

.i-r-ii*im i i.u \

Brent Jungmann Ameren & Director, Nuclear Engineering Welcome Meeting Purpose

. Provide the NRC with information on the upcoming License Amendment Request (LAR) to reflect an updated Criticality Safety Analysis (CSA) for the storage of fuel in the spent fuel pool (SFP) at Callaway Energy Center

. Obtain feedback from the NRC on the proposed LAR to ensure initial submittals address the full desired review scope and minimizes the need for RAIs

. Mutual understanding ofthe proposed schedule and corresponding

, out? ?ç at jn order to ensureadequate NR C. ..

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Team Members Am eren MISSOURI Callaway Enerqy Center Presenters in Bold Ameren Team Titles Holtec Team Titles Members Members Brent Jungmann Senior Director, Nuclear Debu Majumdar Vice President of Engineering Engineering Analysis

• p Dan Pallardy Manager, Design Engineering Stefan Anton Senior Vice President of Brian Richardson Supervising Engineer, Reactor Engineering Engineering I Safety Analysis I Fuels Vadyrn Makodym Engineering Analyst Deborah Farnsworth Sr. Director, Nuclear Plant Support Todd Witt Manager, Regulatory Affairs Jameson Hetrick Engineering Analyst I

Tom Etwood Supervising Engineer, Regulatory rBrian DiPaolo Adjunct Program Manager Affairs Chris Ehmke Reactor Engineering Don Rickard Consultant Licensing Engineer I Jim Mclnvale Consultant Reactor Engineer A

Arenda MISSOURI Callaway Enetqy Center Project Purpose I Background OSA Description Technical Specification Changes Schedule Questions

Project Purpose I Background

. Callaway LFA I VQP Program for Framatome GAlA Fuel

. Need Assessment for RevseU Spent Fuel Pool Criticality Analysis AOR can require credit for ntegraI absorbers in some cases AOR uses depletion parameters specific to incumbent fuel

. Compliance with Reg Guide I 240, Fresh and Spent Fuel Criticality Analyses

. Acceptance Criteria 10 CFR 5c168(b)(4)

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Spent Fuel Pool Storage Description CII

. Current Spent Fuel Storage Racks Approved for installation in 1999 with a criticality analysis that remains the Analysis of Record I 5 high density storage racks incorporating BORALTM fixed neutron absorber Incumbent fuel is Westinghouse 17x17 Standard, Optimized, & Vantage

. No physical changes are being proposed to the Spent Fuel Pool

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Spent Fuel Pool Storage Description en

. AOR primary analysis was for Mixed Zone Three Region storage The whole SEP can be loaded (no reserved empty cells) with conditions Region I assemblies must be stored on the periphery of the racks

. Region I assemblies must be isolated from one another by one or more high burnup, Region 2 assemblies

. The periphery row of alternating Region I & 2 assemblies must be isolated from internal, Region 3 assemblies by one or more Region 2 assemblies A conventional, checkerboard configuration for Region I fuel was also analyzed

Spent Fuel Pool Storage Description (Continued)

I Region I

. Region 2 0 Region 3 mi***ws

CSA Summary of Changes

. Alignment with current regulatory standards

. Explicitly model Framatome GAlA fuel design Remove credit for integral absorbers

. Simplify storage configurations Add credit for cooling time and soluble boron

. Reduce credit for fixed neutron absorber

Technical Specification Changes Ameren MISSOURI Callaway Energy Center

. TS 3716, Fuel Storage Pool Boron Concentration LCO 31.16 The fuel storage pool boron concentration shall be 2165 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.

Conforming change to delete Required Action A.2. I and A.2.2 A.24- Initiate action to restore lmmediately fuel storage pool boron concentration to within limit.

A.2.2 Verify by administrative Immediately means that a non-Region I fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.

Technical Specification Changes (continued)

. TS 3.7a17, Spent Fuel Assembly Storage LCO 3.7.17 The combnaton of initial enrichment and burnup of each spent fuel assembly stored in Region 2 or 3 shall be within theAcceptable Domain of Figure 37.17-1 or in accordance with Specification 4.3W 1 I.

Conforming change to SR 3717.1 Frequency

R 3T17 i Verify by administrative means the initial enrichment and Porto storing the burnup of the fuel assembly is in accordance with Figure fuel assembly in 3J17-1 or Specification 43i.1. Region 2 or 3 Figure 37.17-1 Minimum Required Fuel Assembly Burnup As a Function of Initial Enrich ment to Permit Storage in Regions 2 and 3, will remove reference to Region 3 and reflect differe nt loading curves based on Fuel Assembly Cooling Time Continued

Technical Specification Changes (continued) Am eren MISSOURI I Callaway Enerqy Center Figure aT-If-I Revision 50000 D AC EPTAB E BURNUP D MAIN FOR REGIO 2 AN ) 3 S ORAGE 45000 40000 ---- z:::::;

fz U)0 350O0 -

E 0

Ui Ui 30000 7

/ - z 3o F-I -: / o 25000 D c-i ci 20000

>- E 1

Ui 15000 U)

U) lc 7

4 Ui D

Ui 7 UNAC :EPTAI LE SU NUP I OMAIN FOR EGION 2 OR 3 STO AGE 2.5 3.0 3.5 40

• 4.5

• 5.0

::: ;:::: FUEL ASSEMBLY INITIAL ENRICHMENT (w/o U235)  :: 20 2.5 3.0 3.5 45 FUE+/-I ASI1b/ lrtiai Em chi,nt. vvt% 2tJ 45 50

Technical Specification Changes (continued) f°11 TS 431 Criticality

. TS 43.11 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum nominal U-235 enrichment of 5O weight percent. For fuel with enrichments greater than 4.6 nominal weight percent of U-235, the combination of enrichment and integral fuel burnable absorbers shall be sufficient so thatthe requirements of 4.3.1 .1 .b are met.

b. keff 0.95 < I .0 if fully flooded with unborated water and keff 0.95 if flooded with borated water, which includes an allowance fr uncertainties as described in Section 9.1 of the FSAR; V

c. A nominal 8.99 inch center to center distance between fuel assemblies placed in the fuel storage racks; continued on next slide

Technical Specification Changes (continued) Cn

. TS43mt1 changes continued:

d. Partially spent fuel assemblies with a discharge burnup in the Acceptable Burnup Domain for Region 2 and 3 storage of Figure 3 .7. 1 7- 1 may be allowed unrestricted storage in the fuel storage racks, except for the empty cells in the checkerboarding configuration (Region 1);

e. Deleted Partially spent fuel assemblies with a discharge bumup in the Acceptable Bürnup Domain for Region 3 Storage offigure 3.7.17 may be allowed unrestr icted storage, except for the empty cells in the checkerboarding configuration, and except in Region 2 locations in a Mixed Zone Three Region configuration in the fuel storage racks; and f New or partially spent fuel assemblies with a discharging burnup in the Unacceptable Burnup Domain for Region 2 or 3 Storage of Figure 3.7.17-1 will be stored in Region 1.

Sch dul  ; Am eren MISSOURI Callaway Energy Center

. LAR submittal August 30, 2022 Pre-submittal Meeting June 28, 2022 Ameren/Holtec can support NRC Audit, if requested

. Requested NRC approval of LAR June 23, 2023 Supports Receipt of GAlA Fuel for Operating Cycle 27 RFO begins October 2, 2023

wAffleren Callaway MISSOURI Enetqy Center Discussion, Feedback or Questions

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